Letter Sequence Response to RAI |
|---|
|
|
MONTHYEARML0425301502004-08-27027 August 2004
Station,Technical Specification Change Request No. 331 - Safety Limit Minimum Critical Power Ratio
Project stage: Other
ML0427401722004-09-21021 September 2004
E-mail from Proposed Amendment Re. Cycle 20 SLMCPR
Project stage: Other
ML0425900052004-09-21021 September 2004
Request for Withholding Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML0430003072004-10-19019 October 2004
Technical Specification Change Request No. 331 - Safety Limit Minimum Critical Power Ratio Response to Request for Additional Information
Project stage: Response to RAI
ML0432200942004-11-16016 November 2004
Tech Spec Page for Amendment No. 252, Safety Limit Minimum Critical Power Ratio
Project stage: Other
ML0430305822004-11-16016 November 2004
Issuance of License Amendment No. 252, Safety Limit Minimum Critical Power Ratio
Project stage: Approval
2004-11-16
[Table View] |
|
|---|
Category:Letter
MONTHYEARML23342A1162024-01-0909 January 2024
Independent Spent Fuel Storage Installation Security Inspection Plan
L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023
Proof of Financial Protection 10 CFR 140.15
IR 05000219/20230022023-11-0909 November 2023
EA-23-076 Oyster Creek Nuclear Generating Station - Notice of Violation and Proposed Imposition of Civil Penalty - $43,750 - NRC Inspection Report No. 05000219/2023002
ML23286A1552023-10-13013 October 2023
Defueled Safety Analysis Report (DSAR)
ML23249A1212023-09-0606 September 2023
NRC Inspection Report 05000219/2023002, Apparent Violation (EA-23-076)
ML23242A1162023-08-30030 August 2023
Biennial 10 CFR 50.59 and 10 CFR 72.48 Change Summary Report January 1, 2021 Through December 31, 2022
ML23214A2472023-08-22022 August 2023
NRC Inspection Report 05000219/2023002
IR 05000219/20230012023-05-31031 May 2023
NRC Inspection Report No. 05000219/2023001
IR 07200015/20234012023-05-16016 May 2023
NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2023401
ML23114A0912023-04-24024 April 2023
Annual Radioactive Effluent Release Report for 2022
ML23114A0872023-04-24024 April 2023
Annual Radioactive Environmental Operating Report for 2022
L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023
HDI Annual Occupational Radiation Exposure Data Reports - 2022
L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023
Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML23088A0382023-03-29029 March 2023
Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance
ML22361A1022023-02-24024 February 2023
Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities
IR 05000219/20220022023-02-0909 February 2023
NRC Inspection Report No. 05000219/2022002
ML23031A3012023-02-0808 February 2023
Discontinuation of Radiological Effluent Monitoring Location in the Sewerage System
ML23033A5052023-02-0202 February 2023
First Use Notification of NRC Approved Cask RT-100
ML23025A0112023-01-24024 January 2023
LLRW Late Shipment Investigation Report Per 10 CFR 20, Appendix G
ML22347A2732022-12-21021 December 2022
Independent Spent Fuel Storage Installation Security Inspection Plan Dated December 21, 2022
ML22297A1432022-12-15015 December 2022
Part 20 App G Exemption Letter
L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022
Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15
IR 07200015/20224012022-12-0606 December 2022
NRC Independent Spent Fuel Storage Installation Security Inspection Report 07200015/2022401 (Letter & Enclosure 1)
ML22280A0762022-11-0202 November 2022
Us NRC Analysis of Holtec Decommissioning Internationals Funding Status Report for Oyster Creek, Indian Point and Pilgrim Nuclear Power Station
ML22276A1762022-10-24024 October 2022
Decommissioning International Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages
ML22286A1402022-10-13013 October 2022
NRC Confirmatory Order EA-21-041
IR 05000219/20220012022-08-11011 August 2022
NRC Inspection Report 05000219/2022001
ML22215A1772022-08-0303 August 2022
Decommissioning International (HDI) Proposed Revisions to the Quality Assurance Program Approval Forms for Radioactive Material Packages
ML22214A1732022-08-0202 August 2022
Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E
ML22207B8382022-07-26026 July 2022
NRC Confirmatory Order EA-21-041
ML22130A6882022-05-10010 May 2022
Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G
L-22-026, Occupational Radiation Exposure Data Report - 20212022-04-29029 April 2022
Occupational Radiation Exposure Data Report - 2021
ML22118A6122022-04-28028 April 2022
Annual Radioactive Environmental Operating Report for 2021
ML22118A5822022-04-28028 April 2022
Annual Radioactive Effluent Release Report for 2021
ML22091A1062022-04-0101 April 2022
Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3))
L-22-022, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.2022-03-25025 March 2022
and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations - Holtec.
ML22069A3762022-03-10010 March 2022
Late LLRW Shipment Investigation Report Pursuant to 10 CFR 20, Appendix G
ML22032A0582022-03-0808 March 2022
EA-21-139; EA-150: Oyster Creek Nuclear Generating Station - NRC Investigation Report Nos.. 1-2021-002 & 1-2021-014
ML22060A2202022-03-0202 March 2022
NRC Office of Investigations Case No. 1-2021-009
ML22049B2452022-02-19019 February 2022
Late Low Level Radwaste Shipment Report Pursuant to 10 CFR 20 Appendix G
IR 05000219/20214022022-01-26026 January 2022
EA-21-041: Confirmatory Order Related to Oyster Greek Nuclear Generating Station - NRC Investigation Report I-2020-007; NRC Inspection Report Nos. 05000219/2021402 & 07200015/2021401
ML22025A3422022-01-25025 January 2022
and Big Rock Point - Changes to Site Organization
ML22025A2182022-01-25025 January 2022
Late LLRW Shipments Investigation Report Pursuant to 10 CFR 20, Appendix G
ML22021B5512022-01-21021 January 2022
Compensatory Measures Not Implemented Per Site'S Physical Security Plan Due to Multiplexer (Mux) Power Supply Failure
L-21-134, and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations2021-12-17017 December 2021
and Indian Point Nuclear Generating Stations 1, 2, & 3 - Report on Status of Decommissioning Funding for Independent Spent Fuel Storage Installations
ML21349A5192021-12-15015 December 2021
Commitment Change Summary Report
ML21285A1912021-11-30030 November 2021
Nrc'S Analysis of Holtec Decommissioning International'S Decommissioning Funding Status Report for Oyster Creek Nuclear Generating Station and Pilgrim Nuclear Power Station, Docket Nos 50-219 and 50-293
IR 05000219/20210032021-11-16016 November 2021
NRC Inspection Report No. 05000219/2021003
L-21-118, Changes to Signature Authority & Addressee for Holtec Decommissioning International, LLC Correspondence Re to Oyster Creek Nuclear Generating Station, Pilgrim Nuclear Power Station, Indian Point Nuclear Generating Units 1, 2, 3, & Palisades2021-11-0909 November 2021
Changes to Signature Authority & Addressee for Holtec Decommissioning International, LLC Correspondence Re to Oyster Creek Nuclear Generating Station, Pilgrim Nuclear Power Station, Indian Point Nuclear Generating Units 1, 2, 3, & Palisades
IR 05000219/20214042021-08-26026 August 2021
NRC Independent Spent Fuel Storage Security Inspection Report No. 07200015/2021402 and Security Decommissioning Inspection Report 05000219/2021404 - (Public)
2024-01-09
[Table view] |
Text
10 CFR 50.90 October 19, 2004 21 30-04-20248 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
Technical Specification Change Request No. 331 - Safety Limit Minimum Critical Power Ratio Response to Request for Additional Information
References:
- 1) Letter from C. N. Swenson (AmerGen Energy Company, LLC) to USNRC, dated August 27, 2004
- 2) Letter from C. N. Swenson (AmerGen Energy Company, LLC) to USNRC, dated October 11, 2004 In the Reference 1 letter, AmerGen Energy Company, LLC (AmerGen), requested an amendment to the Technical Specifications (TS), Appendix A of Operating License No.
DPR-16 for Oyster Creek Generating Station (OCGS). This proposed change will revise Technical Specification (TS) Section 2. I .A to incorporate revised Safety Limit Minimum Critical Power Ratios (SLMCPRs) due to the cycle specific analysis performed by Global Nuclear Fuei for OCGS, Cycle 20.
On October I , 2004 and October 19, 2004, conference calls were held with NRC Staff regarding our request. Reference 2 provided our response to questions discussed during the October 1 2004 call. Attached is our response to the questions discussed on the October 19: 2004 call. This information is being submitted under unsworn declaration.
One (1) commitment is contained within this letter, as discussed in Attachment 2.
If you have any questions OF require additional information, please contact Tom Loomis at (610)T65-5510.
I declare under penalty of perjury that the foregoing is true and correct.
Respectfully,
OCGS License Amendment Request October 19, 2004 Page 2 Attachments: 1- Response to Request for Additional Information 2-Commitment cc: S. J. Collins, Administrator, USNRC Region I P. S. Tam, USNRC Senior Project Manager, Oyster Creek R. J. Summers, USNRC Senior Resident inspector, Oyster Creek File No. 02079
OCGS License Amendment Request October 19, 2004 Page 3 cc: Mr. Kent Tosch, Director Bureau of Nuclear Engineering Department of Environmental Protection CN 415 Trenton, NJ 08628 The Honorable John Parker Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731
ATTACHMENT 1 OYSTER CREEK GENERATING STATION DOCKET NO. 50-219 LICENSE NO. DPR-16 lnformatio equest for ~dditiQnal
Attachment 1 Page 1 of I Question:
Explain how Oyster Creek Generating Station (OCGS) will insure that the calculated SLMCPR will remain bounding for ail operating conditions.
Answer:
Oyster Creek Generating Station (OCGS) will operate within the analyzed operating domain, including both off-rated and rated power/ flow conditions (i.e.,
bounded by the rod lines analyzed for SLMCPR), to ensure that the calculated SLMCPR remains bounding throughout Cycle 20. For both off-rated and rated power/flow conditions there is reasonable confidence that the nominal rod patterns utilized by OCGS will produce MCPR distributions less severe than those assumed in the SLMCPR calculations. The more severe MCPR distributions assumed in the SLMCPR calculations produce a more conservative SLMCPR value than would be produced if the SLMCPR were calculated with the nominal rod patterns.
Question:
Explain the basis for the R-factor as provided in the August 27, 2004 Technical Specification Change Request.
Response
At this time, there is no evidence that Oyster Creek Generating Station is experiencing control blade corrosion-induced channel bow. The extra conservative R-factor uncertainty as provided in the Technical Specification Change Request generically accounts for increased channel bow as observed in some ~ W R / 4C-lattice, BWR/5 and BWR/6 reactors. Since no evidence of control blade corrosion-induced bow has been seen for the Oyster Creek Generati~gStation, use of the higher uncertainty is conservative relative to the methodology and uncertainties that have been previously reviewed and approved generically by the NRC. In the event that Oyster Creek Generating Station conclusively experiences channel bow, justification for the higher R-factor uncertainty will be provided to the NRC for review.
ATTACHMENT 2 OYSTER CREEK GENERATING STATION DOCKET NO. 50-219 LICENSE NO. DPR-16
Attachment 2 Page 1 of 1 IT The f o ~ ~ ~ table w i ~ identifies g commitments made in this document. (Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRCs information and are not regulatory commitments.)
In the event that Oyster Creek Generating Station conclusively By Refueling Outage experiences channel bow, justification for the higher R-factor 21 (Fall 2006) uncertainty will be provided to the NRC for review.